M. Reinelt, K. Schmid, K. Krieger SEWG High-Z Ljubljana 01.10.2009 Max-Planck-Institut für Plasmaphysik EURATOM Association, Garching b. München, Germany.

Slides:



Advertisements
Similar presentations
Chapter 2 Chemistry of Life
Advertisements

Report IPP Garching EU Task Force PWI Meeting, Cadarache Oct Max-Planck-Institut für Plasmaphysik compiled by Arne Kallenbach (IPP - EU-PWI.
Report on SEWG mixed materials EU PWI TF meeting Madrid 2007 V. Philipps on behalf of SEWG members Mixed material formation is a among the critical ITER.
R. Doerner, Oct. 18, 2005 EU PWI TF meeting, France Beryllium and carbon mixed-material studies R. P. Doerner, M. J. Baldwin, J. Hanna and D. Nishijima.
A new look at the specification of ITER plasma wall interaction and tritium retention J. Roth a, J. Davis c, R. Doerner d, A. Haasz c, A. Kallenbach a,
Max-Planck-Institut für Plasmaphysik EURATOM Assoziation Interaction of nitrogen plasmas with tungsten Klaus Schmid, A. Manhard, Ch. Linsmeier, A. Wiltner,
WP10-PWI (02)/TEKES/BS(PS) Characterization of retention mechanisms in AUG Monitoring meeting of the EFDA PWI SEWG on Gas Balance and Fuel Retention,
SEWG Meeting HIGH-Z, Ljubljana, October 2009 I. Tungsten distribution on limiters after WF 6 injection in TEXTOR II. SEM and EDX of Melted Tungsten Rods.
Kazuyoshi Sugiyama, SEWG meeting, Culham, July Outline: 1.Introduction 2.Experimental procedure 3.Result 4.Summary Kazuyoshi Sugiyama First.
K. Krieger, SEWG Meeting on Material Migration and ITER Material Mix, JET, Max-Planck-Institut für Plasmaphysik Carbon local transport and redeposition.
Max-Planck-Institut für Plasmaphysik EURATOM Assoziation K. Schmid SWEG Deuterium retention in graphite samples exposed to beryllium-seeded.
Vienna University of Technology (TU Wien) slides provided by F. Aumayr EURATOM – ÖAW: Contribution of the Austrian Fusion Association 2006 Innsbruck University.
SEWG Fuel Retention July 2008 © Matej Mayer Fuel retention in ASDEX Upgrade tungsten coatings M. Mayer, M. Balden, K. Krieger, S. Lindig, O. Ogorodnikova,
CIPS SEWG FR, JET 2008C. Hopf O 2 /He glow discharge cleaning: Experience at IPP Christian Hopf, Volker Rohde, Wolfgang Jacob Max-Planck-Institut für Plasmaphysik.
Kazuyoshi Sugiyama, SEWG meeting on Fuel retention, Garching, July Contribution of Boron on the D retention in the AUG full-W wall regime Max-Planck-Institut.
SEWG Gas Balance 2007 © Matej Mayer First results on deuterium depth profiling in W tiles M. Mayer 1, V.Kh. Alimov, V. Rohde 1, J. Roth 1, A. Herrmann.
D retention and release behaviour of Be/C/W mixed materials
Max-Planck-Institut für Plasmaphysik EURATOM Assoziation K. Schmid SEWG meeting on mixed materials Parameter studies for the Be-W interaction Klaus Schmid.
SEWG Meeting Mixed Materials 2007 First results from beryllium on carbon Florian Kost Christian Linsmeier.
Thomas Härtl, IPP, Measurement of Gas Retention in AUG, WP10-PWI /II/BS, 19. July Measurement of Gas Retention in ASDEX Upgrade - A Technical.
Institute for Plasma Physics Rijnhuizen D retention in W and mixed systems in Pilot-PSI G. De Temmerman a, K. Bystrov a, L. Marot b, M. Mayer c, J.J. Zielinski.
6 th EU PWI TF Meeting Madrid, Oct Tritium Inventory in ITER: Laboratory data and extrapolation from tokamaks Th Loarer, J Roth, S Brezinsek, A.
Benchmarking DIVIMP-ERODEPDIF ITER predictions on material mixing using JET results M. Reinelt, K. Schmid, K. Krieger Max-Planck-Institut.
D retention in O-covered and pure beryllium
Lecture 20: Laminar Non-premixed Flames – Introduction, Non-reacting Jets, Simplified Description of Laminar Non- premixed Flames Yi versus f Experimental.
Flamelet-based combustion model for compressible flows
MAE 5310: COMBUSTION FUNDAMENTALS
Laminar Premixed Flames and Diffusion Flames
Plasma-Electrode interactions in high- current-density plasmas Edgar Choueiri (Princeton) & Jay Polk (NASA-JPL) 3.
Dept of Chemical and Biomolecular Engineering CN2125E Heat and Mass Transfer Dr. Tong Yen Wah, E , (Mass Transfer, Radiation)
1 EFFECTS OF CARBON REDEPOSITION ON TUNGSTEN UNDER HIGH-FLUX, LOW ENERGY Ar ION IRRADITAION AT ELEVATED TEMPERATURE Lithuanian Energy Institute, Lithuania.
About Estuarine Dynamics
Y. Ueda, M. Fukumoto, H. Kashiwagi, Y. Ohtsuka (Osaka University)
19th March 2004 Advances in FC Modeling for Control System Development1 Advances in Fuel Cell Modeling for Control System Development F. Grasser Prof.
Divide yourselves into groups of three (3). Write your names and your complete solution into your answer sheet, and box / encircle your final answer.
Deuterium retention mechanisms in beryllium M. Reinelt, Ch. Linsmeier Max-Planck-Institut für Plasmaphysik EURATOM Association, Garching b. München, Germany.

Lecture 11.0 Etching. Etching Patterned –Material Selectivity is Important!! Un-patterned.
Fabrice Laturelle, Snecma Moteurs
R. Doerner, IAEA CRP on H in Materials, Vienna, Sept. 26, 2006 Mixed-material studies in PISCES-B R. P. Doerner, M. J. Baldwin, J. Hanna and D. Nishijima.
Measurement and modeling of hydrogenic retention in molybdenum with the DIONISOS experiment G.M. Wright University of Wisconsin-Madison, FOM – Institute.
Section 3.1 Properties of Matter
Chapter 2 Chemistry of Life
WHAT CAN KINETICS LEARN FROM NONSTATIONARY THERMODYNAMICS Miloslav Pekař Faculty of Chemistry Institute of Physical and Applied Chemistry Brno University.
Daniel Wamwangi School of Physics
TEC Trilateral Euregio Cluster 1 S. Brezinsek Spectroscopic determination of carbon erosion yields and the composition of chemically eroded molecular carbon.
W coating of CFC tiles for the JET new wall - Task Agreement: JW6-TA-EP2-ILC-05 Manufacturing and testing of W-coated CFC tiles for installation in JET.
Transport of deuterium - tritium neutrals in ITER divertor M. Z. Tokar and V.Kotov Plasma and neutral gas in ITER divertor will be mixed of deuterium and.
Sputter deposition.
1 Max-Planck-Institut für Plasmaphysik 10th ITPA meeting on SOL/Divertor Physics, 8/1/08, Avila ELM resolved measurements of W sputtering MPI für Plasmaphysik.
Introduction of 9th ITPA Meeting, Divertor & SOL and PEDESTAL Jiansheng Hu
Copyright © by Holt, Rinehart and Winston. All rights reserved. ResourcesChapter menu Chemistry of Life Chapter 2 Table of Contents Section 1 Composition.
Copyright © by Holt, Rinehart and Winston. All rights reserved. ResourcesChapter menu To View the presentation as a slideshow with effects select “View”
Edge-SOL Plasma Transport Simulation for the KSTAR
The effect of displacement damage on deuterium retention in plasma-exposed tungsten W.R.Wampler, Sandia National Laboratories, Albuquerque, NM R. Doerner.
Chemistry of Life Chapter 2 Table of Contents Section 1 Composition of Matter Section 2 Energy Section 3 Water and Solutions.
Section 5: Thin Film Deposition part 1 : sputtering and evaporation
1 ITC-22, November 2012, Toki, Japan 1 Modelling of impurity transport, erosion and redeposition in fusion devices: applications of the ERO code A. Kirschner.
Sebastian Höfner, H. Sierks, J.B. Vincent, J. Blum
How to Use This Presentation
Mass Transfer transport of one constituent from a region of higher concentration to that of a lower concentration.
Jari Koskinen, Sami Franssila
Estuarine models: what is under the hood?
Chapter 1 Matter and Change.
ITERに係わる原子分子過程 Atomic and Molecular Processes in ITER SHIMADA, Michiya ITER International Team Annual Meeting of Japan Society of Plasma Science and Nuclear.
1.6 Glow Discharges and Plasma
Aerosol Production in Lead-protected and Flibe-protected Chambers
Mikhail Z. Tokar and Mikhail Koltunov
Quasi-steady-state conditions in JET-ILW:
Chemical Reactions.
Presentation transcript:

M. Reinelt, K. Schmid, K. Krieger SEWG High-Z Ljubljana Max-Planck-Institut für Plasmaphysik EURATOM Association, Garching b. München, Germany Extended grid DIVIMP erosion deposition modelling

Outline Question: Steady state surface composition of the ITER first wall ? Our conceptual approach & strategy Standard and extended grids for DIVIMP Modeling of material mixing Modeling of plasma impurity generation Modeling of chemical phase formations "Work in progress" Question: Steady state surface composition of the ITER first wall ? Our conceptual approach & strategy Standard and extended grids for DIVIMP Modeling of material mixing Modeling of plasma impurity generation Modeling of chemical phase formations "Work in progress"

Motivation What are the steady state surface concentrations of the ITER first wall ? Initial surface composition Initial surface composition Plasma impurity concentration Plasma impurity concentration Erosion by hydrogen Bulk material Bulk material Temperature Re-deposition Erosion by impurities and self sputtering Deposition Plasma transport Sublimation Diffusion Phase formations Layer growth Dynamic surface composition Dynamic surface composition Steady state surface: Total flux balance Steady state surface: Total flux balance

Simplifications Assumption 1: Plasma transport is instantaneous Erosion by hydrogen Re-deposition Erosion by impurities and self sputtering Deposition INSTANT Plasma transport Sublimation Dynamic surface composition Dynamic surface composition Bulk material Bulk material Temperature Diffusion Phase formations Layer growth

Simplifications Erosion by hydrogen Temperature Re-deposition Erosion by impurities and self sputtering Deposition INSTANT Plasma transport Sublimation Diffusion Phase formations Layer growth CONSTANT bulk composition Dynamic surface composition Dynamic surface composition Assumption 1: Plasma transport is instantaneous Assumption 2: Bulk composition is constant All processes depend primarily on the concentrations in the near surface region. All processes depend primarily on the concentrations in the near surface region.

Conceptual approach DIVIMP Plasma transport of impurities Expected results: * Steady state wall concentrations & erosion fluxes * Plasma impurity concentrations Benchmark results with JET experiments Extrapolate to ITER ERODEPDIF: Flux balances ERODEPDIF: Flux balances Background plasma OEDGE (OSM) OEDGE (OSM) SOLPS (B2+Eirene) SOLPS (B2+Eirene) CARRE, recent codes CARRE, recent codes Grid Diffusion Sublimation Chemical phase formation Impurity generation SDTrim Materials properties Materials properties

Conceptual approach DIVIMP Plasma transport of impurities ERODEPDIF: Flux balances ERODEPDIF: Flux balances Background plasma OEDGE (OSM) OEDGE (OSM) SOLPS (B2+Eirene) SOLPS (B2+Eirene) CARRE, recent codes CARRE, recent codes Grid Diffusion Sublimation Chemical phase formation Impurity generation SDTrim Materials properties Materials properties

Conceptual approach DIVIMP Plasma transport of impurities ERODEPDIF: Flux balances ERODEPDIF: Flux balances Background plasma OEDGE (OSM) OEDGE (OSM) SOLPS (B2+Eirene) SOLPS (B2+Eirene) CARRE, recent codes CARRE, recent codes Grid Diffusion Sublimation Chemical phase formation Impurity generation SDTrim Materials properties Materials properties

Extended grid (EG) JET SG (Standard grid) JET SG (Standard grid) JET EG [1] (Extended grid) JET EG [1] (Extended grid) [1] By S. Lisgo

Extended grid (EG)... to be filled with plasma

Conceptual approach DIVIMP Plasma transport of impurities ERODEPDIF: Flux balances ERODEPDIF: Flux balances Background plasma OEDGE (OSM) OEDGE (OSM) SOLPS (B2+Eirene) SOLPS (B2+Eirene) CARRE, recent codes CARRE, recent codes Grid Diffusion Sublimation Chemical phase formation Impurity generation SDTrim Materials properties Materials properties Material mixing model

Material mixing Plasma Each tile receives a flux due to erosion & re-deposition from other tiles Plasma transport is characterized by a re-deposition matrix: Flux of material m on tile i: Result: Set of n coupled differential / algebraic equations Concept: The first wall is divided into n tiles

Mixed material formation Plasma BulkReaction zone Background plasma Concept: Each tile is composed of a thin reaction zone and a bulk material Allows layer growth and erosion, sublimation and simplified chemistry. No diffusion! * Constant thickness Collision cascades: < 50 nm * Variable composition * Constant source / sink * Constant composition

Mixed material formation Bulk For n-tiles and k-chemical phases: kn coupled differential equations First tests with Mathematica: Works for >1000 coupled equations For n-tiles and k-chemical phases: kn coupled differential equations First tests with Mathematica: Works for >1000 coupled equations dσ X / dt = Plasma +Influx (by re-deposition matrix) – Erosion flux (by hydrogen and impurities) – Flux of sublimation (from vapor pressure of the chemical phase) ± Balancing flux (with bulk material) k Chemical phases or elements [X] [Y] [Z]... Chemical reactions +Flux of formation reactions (X is Product) – Flux of dissociation reactions (X is Reactant) Concept: Each tile is composed of a thin reaction zone and a bulk material

Prove-Of-Principle (w/o chemical reactions) Numerical solution for 69 tiles, re-deposition matrix and C wall + Be evaporation Initial Be coverage Re-deposition of Be

Prove-Of-Principle (w/o chemical reactions) Numerical solution for 69 tiles, re-deposition matrix and C wall + Be evaporation Initial Be coverage Re-deposition of Be Be is covered by C

Prove-Of-Principle (w/o chemical reactions) Numerical solution for 69 tiles, re-deposition matrix and C wall + Be evaporation [Be / Ǻ 2 ] Time [s] Tiles with Be at surface Tiles with C at surface All Be is covered by C

Conceptual approach DIVIMP Plasma transport of impurities ERODEPDIF: Flux balances ERODEPDIF: Flux balances Background plasma OEDGE (OSM) OEDGE (OSM) SOLPS (B2+Eirene) SOLPS (B2+Eirene) CARRE, recent codes CARRE, recent codes Grid Diffusion Sublimation Chemical phase formation Impurity generation SDTrim Materials properties Materials properties Model of surface chemistry

ITER first wall He Be W W C C O O H H N N Elements

ITER first wall He Nitrides: WN Be 3 N 2 Nitrides: WN Be 3 N 2 Hydrides: BeH 2 C X H Y OH 2 Hydrides: BeH 2 C X H Y OH 2 Carbides: WC, W 2 C Be 2 C Carbides: WC, W 2 C Be 2 C Beryllides: Be 2 W, Be 12 W Beryllides: Be 2 W, Be 12 W Oxides: WO 3 BeO CO 2 Oxides: WO 3 BeO CO 2 Be W W C C O O H H N N Elements Binary phases

ITER first wall He Nitrides: WN Be 3 N 2 Nitrides: WN Be 3 N 2 Hydrides: BeH 2 C X H Y OH 2 Hydrides: BeH 2 C X H Y OH 2 Carbides: WC, W 2 C Be 2 C Carbides: WC, W 2 C Be 2 C Beryllides: Be 2 W, Be 12 W Beryllides: Be 2 W, Be 12 W Oxides: WO 3 BeO CO 2 Oxides: WO 3 BeO CO 2 Be W W C C O O H H N N Tungstates: BeWO 3, BeWO 4 Hydroxides: Be(OH) 2, W(OH) X … Tungstates: BeWO 3, BeWO 4 Hydroxides: Be(OH) 2, W(OH) X … Elements Binary phases Ternary phases

Simplified description of ITERs first wall chemistry Be W C Be 2 C W 2 C WC Be 2 W Be 12 W Be gas BeO O ads WO 3 WO 3,gas Chemical phases Chemical phases 2 Be + C Be 2 C Be 2 C 2 Be + C W + C WC WC W + C 2 W + C W 2 C W 2 C 2 W + C W + 2 Be Be 2 W Be 2 W W + 2 Be W 2 C WC + W WC + W W 2 C Be + O BeO BeO Be + O W + 3 O WO 3 WO 3 W + 3 O Sublimation: Be Be gas WO 3 WO 3,gas O-Adsorption: O 2,gas O ads O ads O 2,gas Elementary reactions Elementary reactions … Equations for reaction fluxes Reaction balances Change of areal density of chemical phase = + all formation reaction fluxes – all dissociation reaction fluxes Couple to plasma transport code

Benchmarking example: W/Be/O XPS XPS experimental data 2.1 nm Be on W (Substrate,pc) mbar O 2 Layered system XPS experimental data 2.1 nm Be on W (Substrate,pc) mbar O 2 Layered system Model Model of coupled reaction equations Elementary processes: O adsorption Be and W oxidation BeO and WO 3 dissociation Be and WO 3 sublimation Be 2 W formation and dissociation Not included: Depth profiles (Homogeneous distributed phases) Model of coupled reaction equations Elementary processes: O adsorption Be and W oxidation BeO and WO 3 dissociation Be and WO 3 sublimation Be 2 W formation and dissociation Not included: Depth profiles (Homogeneous distributed phases)

Summary Set up a scalable model for JET (and ITER) that describes the first wall material evolution as a combination of: + Dynamic impurity generation (Parametrised TRIDYN) + Plasma transport via a static background (DIVIMP) + Some temperature dependent processes (Chemical phase formations, sublimation, directly benchmarked by XPS data) Method: Numerical solution of a set of coupled algebraic differential equations (Mathematica) Result: Time evolution of Surface concentrations (incl. layer growth) Plasma impurity concentrations Erosion and re-erosion fluxes Benchmark the results with JET experiments (e.g. post-mortem analysis of layers, spectroscopy of erosion fluxes)

Erosion and re-erosion by impurities Assumption: Individual sputteryields Y j of a mixture of elements scales linearily with the surface concentration Assumption: Individual sputteryields Y j of a mixture of elements scales linearily with the surface concentration Works well for Be / C but only fairly good for W / C, W / Be 50 eV D eV Be on C (Precalculated Yields)

Re-deposition matrix (JET SG) Promt re-deposition... Simple (unverified) OSM plasma background

Re-deposition matrix by DIVIMP Lauch flux of Be impurity ions and map points of re-deposition (Charge resolved) Re-deposition matrix, n ~ 70 static BGP Bin static BGP, standard grid